Poloidal field (PF) coil system design and R&D for the Burning Plasma Experiment (BPX)

The design for the Burning Plasma Experiment (BPX) poloidal field (PF) coil system has evolved through several stages of machine size and physics requirements. The result has been a firm basis for a conceptual design with a significant R&D supporting activity on critical components. The authors review the characteristics of the latest PF system design and various facets of the R&D activity in the program as the machine has progressed. The BPX PF system design activity has satisfied machine physics requirements and dimensional constraints. Concepts for critical components have been developed to the point where detailed dimensions could begin to be solidified. Mechanical and electrical evaluation of materials, testing of selected components, and development of design criteria have spanned several iterations on machine requirements. This provides a strong basis even for initiating design of a new machine.<<ETX>>

[1]  R. L. Myatt.  Axisymmetric structural simulation of the central solenoid for the Burning Plasma Experiment (BPX) , 1991, [Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering.

[2]  S. Jardin,et al.  Dynamic modeling of transport and positional control of tokamaks , 1986 .

[4]  R. J. Thome,et al.  Poloidal field coil system optimization for the Compact Ignition Tokamak (CIT) , 1989, IEEE Thirteenth Symposium on Fusion Engineering.

[5]  R. J. Thome,et al.  Electrothermal evaluation of conductors for the Compact Ignition Tokamak (CIT) PF coils , 1989, IEEE Thirteenth Symposium on Fusion Engineering.

[6]  R. F. Vieira,et al.  Evaluation of Low Friction Materials for the Central Solenoid of the Compact Ignition Tokamak (CIT) , 1991 .

[7]  W. R. Mann,et al.  Design and R&D for the central solenoid for the Compact Ignition Tokamak (CIT) , 1989, IEEE Thirteenth Symposium on Fusion Engineering.

[8]  B. A. Smith,et al.  Cooldown testing for the BPX central solenoid , 1991, [Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering.